1 EX/P7-12. Transient and Intermittent Magnetic Reconnection in TS-3 / UTST Merging Startup Experiments

Size: px
Start display at page:

Download "1 EX/P7-12. Transient and Intermittent Magnetic Reconnection in TS-3 / UTST Merging Startup Experiments"

Transcription

1 1 EX/P7-12 Transient and Intermittent Magnetic Reconnection in TS-3 / UTST Merging Startup Experiments Y. Ono 1), R. Imazawa 1), H. Imanaka 1), T. Hayamizu 1), M. Inomoto 1), M. Sato 1), E. Kawamori 1), A. Ejiri 1), Y. Takase 1), T. Asai 2), T. Takahashi 2) 1) Graduate School of Frontier Sciences, University of Tokyo, Tokyo, Japan 2) Department of Physics, Nihon University, Tokyo, Japan contact of main author: ono@k.u-tokyo.ac.jp Abstract. The high-power reconnection heating has been developed in the TS-3 merging experiments, leading us to a new pulsed high-beta spherical tokamak (ST) formation. Two ST plasmas were produced inductively by two or four PF coils without using any central solenoid (CS) coil and were merged together for MW-GW reconnection heating. The magnetic reconnection transformed the magnetic energy of reconnecting magnetic field through the outflow kinetic energy finally to the ion thermal energy, increasing the plasma beta of ST up to 0.5. A new finding is that ejection of current sheet (or plasmoid) causes high-speed merging/ reconnection as well as high-power heating. In the high-q ST merging, the sheet resistivity was almost classical due to the sheet thickness much longer than ion gyroradius. Large inflow flux and low current-sheet dissipation resulted in flux pileup followed by rapid growth of the current sheet. When the flux pileup exceeded a critical limit, the sheet was ejected mechanically from the squeezed X-point area. The reconnection (outflow) speed was slow during the flux pileup and was fast during the ejection, indicating that intermittent reconnection similar to the solar flare increased the averaged reconnection speed. These transient effects enable us to have the fast reconnection as well as the high-power reconnection heating, even if the merging high-q tokamaks have low current-sheet resistivity. 1. Introduction We initiated the laboratory experiment of magnetic reconnection in 1986 using two merging spherical tokamaks (STs) and spheromaks and have been studying its mechanisms and applications. For the past 20 years, our TS-3 and TS-4 experiments explored the merging startup of STs and CTs for high-power reconnection heating/ ramp-up without using any center-solenoid (CS) coil[1-7]. Two STs with major radii~0.2m (TS-3), 0.5m (TS-4) were merged together in the axial direction under magnetic compression provided by two PF acceleration coils. The magnetic reconnection was found to transform the magnetic energy of reconnecting magnetic field through the outflow kinetic energy finally to the ion thermal energy, increasing the plasma beta of ST up to 50%. The counterhelicity merging of two spehromaks is now used widely for slow formation of FRC (Field-Reversed Configuration). Transformation of the produced FRC to ultra-highbeta ST was made successfully as the first demonstration of the second-stable ST formation[6,7]. FIG.1. Two merging ST plasmas for reconnection heating and their X-point and current sheet structure. Since 1994, the cohelicity merging of two or three STs has

2 2 EX/P7-12 been demonstrated also in the START experiment for the ST startup[8-11]. Its successful result with neutral beam (NB) heating was extended to the up-scaled experiment MAST and now variety of startup operations have been optimized in MAST[11]. An important question arises as to whether this high-power reconnection heating is still available when high guiding field (high-q) suppresses the anomalous resistivity of current sheet. The fast reconnection mechanism in the high guiding toroidal field B t is left unsolved, which is essential to the high-power heating by reconnection outflow. While this unique method provides the highest heating power MW-GW within short reconnection time among all CS-less startup methods, the guiding field is a main cause to decrease the reconnection speed of merging STs[4-7]. This paper addresses three key issues: (1) fast transient reconnection mechanisms under high guiding field B t condition and comparison with the conventional steady state reconnection like the Sweet-Parker model, (2) current sheet ejection as a fast transient reconnection mechanism, and (3) transformation of the steady reconnection to the transient and intermittent reconnections. We found for the first time that the ejection of current sheet (or plasamoid) similar to the solar flare causes fast reconnection/ merging as well as high-power heating. These facts lead us to a more reactor-relevant merging startup experiment, UTST by use of sets of external coils. 2. Experimental Setups The TS-3 device was used to perform the CS-less startups and merging/ reconnection heating for high-beta STs formation[1-7]. As shown in Fig. 2, its cylindrical vacuum vessel with length of 1m and diameter of 0.8m has two poloidal (PF) coils for poloidal flux injection and two STs with R 0.2m R/a 1.5 were merged together in the axial direction. The plasma heating power of ST merging was ranging from 2MW to 10MW, depending on the guiding field B t [6,7]. Each merging ST initially had plasma parameters: T i T e 10eV, n e m -3 and B 0.5kG. Their merging/ reconnection was accelerated by the PF coil currents provided by the new power crowbar circuit and decelerated by the separation coil currents on the midplane. A CS (or OH) coil with diameter 0.12m was used to provide volt-second only for current sustainment ( 200µsec) after the high-beta ST formation. Seven thin arrays of magnetic pickup coils were inserted on the r-z plane of the vessel to measure directly the 2-D magnetic field profile. A 1m polychrometor with an optical multi-channel analyzer (OMA) was used to measure 2-D profiles of ion temperature T i by means of the Doppler width of helium and carbon impurity lines. An electrostatic probe array was inserted to measure the radial profiles of electron temperature T e and density n e. Poloidal flux contours, profiles of FIG. 2. Cross-section and photo of TS-3 merging device with a pair of PF acceleration coils.

3 3 EX/P7-12 current density and plasma pressure were calculated from the 2-D magnetic field profiles and the profiles of T i, T e and n e. 3. Experimental Results Figure 3(a) shows dependence of reconnection rate γ of two merging STs on the guiding toroidal field B t0 normalized by the constant reconnecting field B //, where γ is defined as growth rate of the reconnected poloidal flux normalized by peak poloidal fluxes of two merging STs. It has been generally observed in TS-3, TS-4, SSX and MRX merging experiments that the reconnection speed decreases with B t0 [2,3,6,12,13]. Its main reason is that anomalous resitivity of current sheet increases significantly when the current sheet (thickness δ) is compressed shorter than the ion gyroradius ρ i. Decrease in compressibility of the current sheet is another reason why γ increases inversely with B t0. Under the present experimental condition, the sheet thickness δ was compressed down to the size of ion gyroradius ρ i when B t0 <2.4 B //. As shown in the black circles in Fig. 3(a), γ was in high level " =1.9 #10 6 [sec -1 ] for B t0 <2.4B // and was in low level " =1.2 #10 6 [sec -1 ] for B t0 >2.4B //, in agreement with the fast reconnection mechanism mentioned above. If this mechanism holds true for all experimental regime, the reconnection speed as well as the outflow speed stay slow under the high B t0 condition. The reconnection heating is determined by reconnection outflow speed proportional to the reconnection inflow speed. For our high-beta ST startup experiment, the first question is whether we can expect the fast inflow/ outflow and significant ion heating during high-q (high-b t0 ) ST merging. In this experiment, two high-q STs were over-compressed axially using the two acceleration PF coils and the capacitor banks with new power-crowbar circuit. Figures 4(a) and (b) show r-z contours of poloidal flux and toroidal current density j t when two merging STs with center q 0 ~2.5 (q 90 ~35) were compressed low and high by the PF acceleration coils. These flux contours were measured by 2- D magnetic probe array on r-z plane whose maximum special resolution was 5mm in z- direction and 40mm in r-direction. In the low compression case (a), shape and position of the current sheet were maintained during the merging, just like the conventional steady-state Sweet-Parker reconnection. However, in the high compression case (b), the current sheet was observed to grow and was ejected inward from the X-point region in sharp contrast with the mentioned quasi-steady case. It is noted that the reconnected flux increased significantly during the sheet ejection in Fig. 4(c). As indicated by the X marks in Fig. 3(a), γ during the ejection was about 2.8 "10 6 [sec -1 ], which was three FIG. 3. The reconnection rates γ (a) and ion temperatures T i (b) as a function of toroidal field B t0 normalized by reconnecting poloidal field B // (constant). The transient γ and T i during the sheet ejection are also plotted. times higher than γ without sheet ejection. Though this high reconnection rate was obtained transiently during the ejection, the time-average reconnection rate was also higher than the steady-state case.

4 4 EX/P7-12 The sheet ejection was observed once or twice, depending on magnetic fluxes of the merging STs. We observed reproducibly the sheet ejection twice, when the initial fluxes of merging STs were larger than 3mWb under the present experimental condition. After the growth and ejection of the current sheet, the same cycle occurred during the second ejection. These facts indicate that intermittent reconnection similar to the solar flare occurs when plasma inflow is over-accelerated by an external coils[14,15]. The sheet ejection was found to increase the time-averaged reconnection rate. It is concluded that the intermittent reconnection caused by the sheet ejection is a new fast reconnection mechanism without using the anomalous resisitivity of the current sheet. A related question is why the sheet was ejected inward in Fig. 4(b). We increased the axial separation length of the two acceleration coils to compress the two merging STs more uniformly. Figure 5(c) shows the r-z contours of poloidal flux and toroidal current density j t of two merging high-q STs under the high uniform compressions. The separation length of the two acceleration coils was 10cm longer than that in Fig. 4(b). It was clearly observed that the upper and lower halves of current sheet were ejected inward and outward respectively, due to more uniform compression. The inward ejection in Fig. 4(b) was due to axial and inward compression provided by the acceleration coils, while inward and outward ejections in Fig. 5(c) were due to the uniform compression. The larger increase in reconnection speed was obtained in the inward ejection case (Fig. 4(b)), probably because the compression force of the coils was not lost for compression and splitting of the sheet but was used mostly for the sheet ejection unlike the uniform ejection case. The second question is whether the Reconnected Flux Ratio [%] After Ejection (c) Before Ejection Case (b) Case (a) Time [!sec] FIG. 4. r-z contours of poloidal fluxes and toroidal current densities j t (by red: positive and blue: negative colors) of two merging high-q STs under the conditions of low and high axial-inward compressions (a) (b) and time evolutions of their reconnected fluxes (c). fast reconnection caused by the current sheet ejection really heats plasma ions under high guiding field B to condition. Figure 3(b) shows peak ion temperatures before and after the ST merging/ reconnection as a function of B to / B //. The ion temperature T i after the reconnection was observed to increase inversely with B t0 /B //, in agreement with the reconnection rate γ. It is simply because the reconnection outflow proportional to reconnection (inflow) speed was transformed into ion thermal energy through fast shock and ion viscosity[6,7]. In the high compression case, T i increased up to 90eV right after the ejection, in sharp contrast with the low compression cases

5 5 EX/P7-12. without sheet ejection. The increase in outflow was found to cause the highpower ion heating. Based on this fact, the sheet ejection enables us to have the fast reconnection as well as the high-power reconnection heating, even if the merging high-q tokamaks have low current-sheet resitivity. Final questions are how the transient effect of reconnection influences the plasma inflow and outflow and how it is related with the steady-state reconnection like the Sweet-Parker model. We varied externally the plasma inflow speed from slow to fast, using the acceleration coil current. Figures 5(a)-(c) show r-z contours of poloidal fluxes and j t for the high compression case (a), the medium compression case (b) and the low compression case (c), respectively. Figures 6(a)-(c) show more detailed evolutions of the inflow fluxes ul and the outflow fluxes V out " for the three cases in Figs. 5, FIG. 5. r-z contours of poloidal fluxes and toroidal current densities j t (by red: positive and blue: negative colors) of two merging high-q STs under the conditions of low, medium and high axial-uniform compressions (a), (b) and (c).

6 6 EX/P7-12 where u, V out are inflow and outflow speeds, L, " are length and thickness of the current sheet. In the low compression case (a), the sheet current was formed from t=0µsec to t=5µsec and was maintained in quasi-steady state from t=5µsec to t=10µsec. In this quasi-steady phase, the inflow flux balanced with the outflow flux. This fact indicates that the quasi-steady reconnection ( db /dt " dn /dt " 0 ) was realized just like the conventional Sweet-Parker model[16]. Its inflow speed is given by u 2 = "V A /µ 0 L, (1) where V A is the Alfven speed. This theoretical velocity agrees with the measured inflow velocity within 30%, if we use the resisitivity " calculated from electric field E t and current density j t at X-point. In the intermediate compression case (b), ul was larger than V out " in the early reconnection phase before t=6µsec and became smaller in the late phase after t=6µsec. This fact indicates that the flux pileup increased early reconnection speed during the formation of the current sheet. The current sheet kept growing until t=6µsec and was deformed significantly after t=6µsec. In the high compression case (c), ul exceeded significantly V out " before t=7µsec, indicating a significant pileup of plasma flux. This pileup caused the formation of large current sheet with round shape. After t=8µsec, V out " became much larger than ul, indicating that huge plasma mass was ejected from the reconnection region. Figure 5(c) indicates that the current sheet was ejected around t=8-10µsec in agreement with this mass ejection time in Fig. 6(c). Since the sheet thickness δ was larger than the gyroradius ρ i, the sheet resistivity η was almost classical in sharp contrast with the large anomalous resitivity of the sheet when δ<ρ i [5,6]. The large inflow flux and low current-sheet dissipation resulted in the flux pileup followed by the rapid growth of the current sheet. When the flux pileup exceeded a critical limit, the sheet was ejected mechanically from the squeezed X-point area. Its reconnection speed became larger than the steady-state Sweet-Parker speed due to the pileup and ejection effects. FIG. 6. Time evolutions of inflow and outflow fluxes ul, V out " under the conditions of (a) high, (b) intermediate and (c) low axialuniform compressions. 4. Discussions The transient effect of magnetic reconnection can be modelled theoretically by extending the conventional Sweet-Parker model. We assume the Sweet-Parker type current sheet with thickness 2δ and length 2L, as shown in Fig. 1. Its basic equations are composed of the magnetic flux dissipation law:

7 7 EX/P7-12 u = ", (2) µ 0 # and the mass conservation law: ul = "V A + L" dn sheet + " n sheet V eject, (3) n 0 dt n 0 where n sheet /n 0 " # is the electron density pileup factor (electron density of the current sheet normalized by the bulk electron density) and V eject is ejection speed of current sheet. The second term represents the mass pileup inside the current sheet and the third term does the sheet (mass) ejection. Based on Eqs. (2) and (3), the inflow velocity is calculated as follows: u 2 = " µ 0 ( V A + 1 dn sheet L n 0 dt + n sheetv eject n 0 L ) (4) The first, second and third terms are the conventional Sweet-Parker term, the mass pileup term and the mass ejection term, respectively. When the forming current sheet works as a plasma sink, the pileup term increases the reconnection (inflow) speed transiently. The following preliminary model helps us to understand how Eq. 4 is connected with the increase in the time-averaged reconnection speed. If we assume the mass pileup and ejection speed as follows for simplicity: " = n sheet /n 0 = " 1 (1+ sin#t), (6) V eject = V 1 {1+ sin("t + #)}, (7) the following inflow speed is obtained: u 2 = " µ 0 L [V + # A1 1$ cos$t + # 1 V 1 sin$t + # 1 Vsin($t + %) + # 1 V 1 + # 1 V 1 sin$t & sin($t + %)].---(8) The last term contains a steady-state component, indicating that the sheet ejection increases the averaged reconnection speed. This term is maximized at " = 0, where the ejection occurs when the pileup factor reaches the maximum value. Even if the anomalous resistivity does not increase, the fast inflow causes the fast reconnection by means of the sheet ejection phenomenon. As the inflow flux is increased, the quasi-steady reconnection is transformed to the transient one and finally to the intermittent one with faster averaged reconnection speed. If we include the transient effect of magnetic field too, we can replace Eq. 2 by u = " µ 0 # + $B R, (5) $t B but lose the analytic solution like Eq. (4), where R is the characteristic scale length. 5. Summary and Upscale of the Merging Startup Experiment In summary, we studied experimentally the transient effects of magnetic reconnection: (1) the pileup effect and (2) the current sheet ejection effect as new fast reconnection mechanisms. When the externally driven plasma inflow flux exceeds the plasma outflow flux, the plasma pileups inside the current sheet, increasing the plasma inflow. As the inflow flux is increased, the quasi-steady reconnection like the Sweet-Parker model is transformed to the transient one and finally to the intermittent one. The transient effects such as the flux pileup and the ejection enable us to have the high reconnection speed as well as the high-power reconnection heating, even if the merging high-q tokamaks have low current-sheet resistivity. We are now up-scaling the mentioned merging startup experiments and also the RF heating/ current drive experiment of TST-2 to a new ST experiment: UTST (R~0.4m). Figure 7 shows the photo and vertical cross-section of the UTST device. Its main objects are to demonstrate (1) the double-null startup of STs without CS coil, (2) their reactor-relevant reconnection heating for high-beta ST formation and (3) their sustainment by advanced RF

8 8 EX/P7-12 and NBI heating/ currentdrive techniques. In order to make the reconnection heating method reactorrelevant, all PF coils are located outside of the vacuum vessel in sharp contrast with TS-3, 4 and MAST whose PF coils are located inside the vacuum vessel. In UTST, two X- points are formed by the two sets of PF coils to form two merging ST plasmas. Figure 8 shows FIG. 7. Photo and vertical cross-section of the UTST device. the preliminary 2-D magnetic probe measurement of vacuum X-point structure produced by two PF coils (PF#1-1 and #1-2). Each pair of PF coils was observed to form and maintain an X-point for 300µsec for the UTST double-null startup and merging scheme. The first plasma discharge will be demonstrated in October after installation of new capacitor bank. The mega-watt heating power of reconnection is expected to transform the initial low-beta merging STs to the high-beta ST (30-50%). [1] ONO, Y., et al., Proc. the 1986 IEEE International Conference on Plasma Science, Saskatoon, Canada, (1986), 77. [2] ONO, Y., et al., Phys Fluids B6 (1993) [3] YAMADA, M., ONO, Y., et al., Phys. Rev. Lett. 65 (1990) 721. [4] ONO, Y., et al., Phys. Rev. Lett. 76 (1996) [5] ONO, Y., et al., Phys. Plasmas 4 (1997) [6] ONO, Y., INOMOTO, M., Phys. Plasmas 7 (2000) [7] ONO, Y., et al., Nucl. Fusion (2003). FIG. 8. r-z contours of vacuum poloidal flux during the double-null point formation at UTST device and its vertical cross-section. [8] SYKES. A., et al., Proc. 21 st EPS Conference on Controlled Fusion and Plasma Physics, European Physical Society, Montpellier, (1994) 22. [9] GRYAZNEVICH, M., et al., Phys. Rev. Lett. 80 (1998) [10] SYKES, A., et al., Fusion Energy 2000, OV4/1, (2001). [11] SYKES, A., et al., Phys. Plasmas 8 (2001) [12] YAMADA, M., et al., Phys. Plasmas 4 (1997) [13] BROWN, M., Phys. Plasmas 6 (1999) [14] YOKOYAMA, T., SHIBATA, K., et al., Nature 375 (1995) 42. [15] MASUDA, S., et al., Nature 371 (1994) 495. [16] JI, H., et al., Phys. Rev. Lett. 80 (1998) 3256.

Ion and Electron Heating Characteristics of Magnetic Reconnection in TS-3 and UTST Merging Startup Experiments

Ion and Electron Heating Characteristics of Magnetic Reconnection in TS-3 and UTST Merging Startup Experiments Ion and Electron Heating Characteristics of Magnetic Reconnection in TS-3 and UTST Merging Startup Experiments Y. Ono 1), R. Imazawa 1), H. Imanaka 1), Y. Hayashi 1), S. Ito 1), M. Nakagawa 1), T. Yamada

More information

Double Null Merging Start-up Experiments in the University of Tokyo Spherical Tokamak

Double Null Merging Start-up Experiments in the University of Tokyo Spherical Tokamak 1 EXS/P2-19 Double Null Merging Start-up Experiments in the University of Tokyo Spherical Tokamak T. Yamada 1), R. Imazawa 2), S. Kamio 1), R. Hihara 1), K. Abe 1), M. Sakumura 1), Q. H. Cao 1), H. Sakakita

More information

High Power Heating of Magnetic Reconnection for High-Beta ST Formation in TS-3 and UTST ST Merging Experiments

High Power Heating of Magnetic Reconnection for High-Beta ST Formation in TS-3 and UTST ST Merging Experiments High Power Heating of Magnetic Reconnection for High-Beta ST Formation in TS-3 and UTST ST Merging Experiments Y. Ono, H. Tanabe, Y. Kamino, K. Yamasaki, K. Kadowaki, Y. Hayashi, T. Yamada, C. Z. Cheng

More information

Experimental Study of Hall Effect on a Formation Process of an FRC by Counter-Helicity Spheromak Merging in TS-4 )

Experimental Study of Hall Effect on a Formation Process of an FRC by Counter-Helicity Spheromak Merging in TS-4 ) Experimental Study of Hall Effect on a Formation Process of an FRC by Counter-Helicity Spheromak Merging in TS-4 ) Yasuhiro KAMINOU, Michiaki INOMOTO and Yasushi ONO Graduate School of Engineering, The

More information

Fast compression of a current sheet during externally driven magnetic reconnection

Fast compression of a current sheet during externally driven magnetic reconnection Earth Planets Space, 53, 521 526, 2001 Fast compression of a current sheet during externally driven magnetic reconnection Y. Ono, M. Inomoto, Y. Ueda, T. Matsuyama, and Y. Murata High Temperature Plasma

More information

Experimental Investigations of Magnetic Reconnection. J Egedal. MIT, PSFC, Cambridge, MA

Experimental Investigations of Magnetic Reconnection. J Egedal. MIT, PSFC, Cambridge, MA Experimental Investigations of Magnetic Reconnection J Egedal MIT, PSFC, Cambridge, MA Coronal Mass Ejections Movie from NASA s Solar Dynamics Observatory (SDO) Space Weather The Solar Wind affects the

More information

Active Stability Control of a High-Beta Self-Organized Compact Torus

Active Stability Control of a High-Beta Self-Organized Compact Torus 1 ICC/P5-01 Active Stability Control of a High-Beta Self-Organized Compact Torus T. Asai 1), Ts. Takahashi 1), H. Matsunaga 1), H. Itagaki 1), Y. Matsuzawa 1), Y. Hirano 1), To. Takahashi 2), M. Inomoto

More information

Additional Heating Experiments of FRC Plasma

Additional Heating Experiments of FRC Plasma Additional Heating Experiments of FRC Plasma S. Okada, T. Asai, F. Kodera, K. Kitano, T. Suzuki, K. Yamanaka, T. Kanki, M. Inomoto, S. Yoshimura, M. Okubo, S. Sugimoto, S. Ohi, S. Goto, Plasma Physics

More information

Plasma formation in MAST by using the double null merging technique

Plasma formation in MAST by using the double null merging technique 1 Plasma formation in MAST by using the double null merging technique P. Micozzi 1, F. Alladio 1, P. Costa 1, A. Mancuso 1, A. Sykes 2, G. Cunningham 2, M. Gryaznevich 2, J. Hicks 2, M. Hood 2, G. McArdle

More information

Non-Solenoidal Plasma Startup in

Non-Solenoidal Plasma Startup in Non-Solenoidal Plasma Startup in the A.C. Sontag for the Pegasus Research Team A.C. Sontag, 5th APS-DPP, Nov. 2, 28 1 Point-Source DC Helicity Injection Provides Viable Non-Solenoidal Startup Technique

More information

D.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd. University of Wisconsin - Madison 1500 Engineering Drive Madison, WI 53706

D.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd. University of Wisconsin - Madison 1500 Engineering Drive Madison, WI 53706 D.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd University of Wisconsin - Madison 1500 Engineering Drive Madison, WI 53706 Concept Overview Implementation on PEGASUS Results Current

More information

Formation and Long Term Evolution of an Externally Driven Magnetic Island in Rotating Plasmas )

Formation and Long Term Evolution of an Externally Driven Magnetic Island in Rotating Plasmas ) Formation and Long Term Evolution of an Externally Driven Magnetic Island in Rotating Plasmas ) Yasutomo ISHII and Andrei SMOLYAKOV 1) Japan Atomic Energy Agency, Ibaraki 311-0102, Japan 1) University

More information

Evolution of Bootstrap-Sustained Discharge in JT-60U

Evolution of Bootstrap-Sustained Discharge in JT-60U 1 Evolution of Bootstrap-Sustained Discharge in JT-60U Y. Takase 1), S. Ide 2), Y. Kamada 2), H. Kubo 2), O. Mitarai 3), H. Nuga 1), Y. Sakamoto 2), T. Suzuki 2), H. Takenaga 2), and the JT-60 Team 1)

More information

Effect of magnetic reconnection on CT penetration into magnetized plasmas

Effect of magnetic reconnection on CT penetration into magnetized plasmas Earth Planets Space, 53, 547 55, 200 Effect of magnetic reconnection on CT penetration into magnetized plasmas Yoshio Suzuki, Takaya Hayashi 2, and Yasuaki Kishimoto Naka Fusion esearch Establishment,

More information

Behavior of Compact Toroid Injected into the External Magnetic Field

Behavior of Compact Toroid Injected into the External Magnetic Field Behavior of Compact Toroid Injected into the External Magnetic Field M. Nagata 1), N. Fukumoto 1), H. Ogawa 2), T. Ogawa 2), K. Uehara 2), H. Niimi 3), T. Shibata 2), Y. Suzuki 4), Y. Miura 2), N. Kayukawa

More information

Overview of Spherical Tokamak Research in Japan

Overview of Spherical Tokamak Research in Japan OV/5-5 26 th IAEA Fusion Energy Conference Kyoto International Conference Center, Kyoto, Japan, 17-22 Oct. 216 Overview of Spherical Tokamak Research in Japan Y. Takase 1, A. Ejiri 1, T. Fujita 2, N. Fukumoto

More information

Evolution of Bootstrap-Sustained Discharge in JT-60U

Evolution of Bootstrap-Sustained Discharge in JT-60U EX1-4 Evolution of Bootstrap-Sustained Discharge in JT-60U Y. Takase, a S. Ide, b Y. Kamada, b H. Kubo, b O. Mitarai, c H. Nuga, a Y. Sakamoto, b T. Suzuki, b H. Takenaga, b and the JT-60 Team a University

More information

Plasma spectroscopy when there is magnetic reconnection associated with Rayleigh-Taylor instability in the Caltech spheromak jet experiment

Plasma spectroscopy when there is magnetic reconnection associated with Rayleigh-Taylor instability in the Caltech spheromak jet experiment Plasma spectroscopy when there is magnetic reconnection associated with Rayleigh-Taylor instability in the Caltech spheromak jet experiment KB Chai Korea Atomic Energy Research Institute/Caltech Paul M.

More information

Magnetic Field Configuration Dependence of Plasma Production and Parallel Transport in a Linear Plasma Device NUMBER )

Magnetic Field Configuration Dependence of Plasma Production and Parallel Transport in a Linear Plasma Device NUMBER ) Magnetic Field Configuration Dependence of Plasma Production and Parallel Transport in a Linear Plasma Device NUMBER ) Daichi HAMADA, Atsushi OKAMOTO, Takaaki FUJITA, Hideki ARIMOTO, Katsuya SATOU and

More information

Flow dynamics and plasma heating of spheromaks in SSX

Flow dynamics and plasma heating of spheromaks in SSX Flow dynamics and plasma heating of spheromaks in SSX M. R. Brown and C. D. Cothran, D. Cohen, J. Horwitz, and V. Chaplin Department of Physics and Astronomy Center for Magnetic Self Organization Swarthmore

More information

Noninductive Formation of Spherical Tokamak at 7 Times the Plasma Cutoff Density by Electron Bernstein Wave Heating and Current Drive on LATE

Noninductive Formation of Spherical Tokamak at 7 Times the Plasma Cutoff Density by Electron Bernstein Wave Heating and Current Drive on LATE 1 EX/P6-18 Noninductive Formation of Spherical Tokamak at 7 Times the Plasma Cutoff Density by Electron Bernstein Wave Heating and Current Drive on LATE M. Uchida, T. Maekawa, H. Tanaka, F. Watanabe, Y.

More information

D.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd. University of Wisconsin - Madison 1500 Engineering Drive Madison, WI 53706

D.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd. University of Wisconsin - Madison 1500 Engineering Drive Madison, WI 53706 D.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd University of Wisconsin - Madison 1500 Engineering Drive Madison, WI 53706 Non-solenoidal startup using point-source DC helicity injectors

More information

Study of local reconnection physics in a laboratory plasma

Study of local reconnection physics in a laboratory plasma Earth Planets Space, 53, 539 545, 2001 Study of local reconnection physics in a laboratory plasma Hantao Ji, Troy Carter, Scott Hsu, and Masaaki Yamada Princeton Plasma Physics Laboratory, Princeton University,

More information

Resistive Wall Mode Control in DIII-D

Resistive Wall Mode Control in DIII-D Resistive Wall Mode Control in DIII-D by Andrea M. Garofalo 1 for G.L. Jackson 2, R.J. La Haye 2, M. Okabayashi 3, H. Reimerdes 1, E.J. Strait 2, R.J. Groebner 2, Y. In 4, M.J. Lanctot 1, G.A. Navratil

More information

Magnetic Reconnection in Laboratory, Astrophysical, and Space Plasmas

Magnetic Reconnection in Laboratory, Astrophysical, and Space Plasmas Magnetic Reconnection in Laboratory, Astrophysical, and Space Plasmas Nick Murphy Harvard-Smithsonian Center for Astrophysics namurphy@cfa.harvard.edu http://www.cfa.harvard.edu/ namurphy/ November 18,

More information

Electrode Biasing Experiment in the Large Helical Device

Electrode Biasing Experiment in the Large Helical Device 1 EXC/P8-07 Electrode Biasing Experiment in the Large Helical Device S. Kitajima 1), H. Takahashi 2), K. Ishii 1), J. Sato 1), T. Ambo 1), M. Kanno 1), A. Okamoto 1), M. Sasao 1), S. Inagaki 3), M. Takayama

More information

Current Drive Experiments in the HIT-II Spherical Tokamak

Current Drive Experiments in the HIT-II Spherical Tokamak Current Drive Experiments in the HIT-II Spherical Tokamak T. R. Jarboe, P. Gu, V. A. Izzo, P. E. Jewell, K. J. McCollam, B. A. Nelson, R. Raman, A. J. Redd, P. E. Sieck, and R. J. Smith, Aerospace & Energetics

More information

Experimental studies of magnetic reconnection*

Experimental studies of magnetic reconnection* PHYSICS OF PLASMAS VOLUME 6, NUMBER 5 MAY 1999 Experimental studies of magnetic reconnection* M. R. Brown Department of Physics and Astronomy, Swarthmore College, Swarthmore, Pennsylvania 19081-1397 Received

More information

Density Collapse in Improved Confinement Mode on Tohoku University Heliac

Density Collapse in Improved Confinement Mode on Tohoku University Heliac 1 EX/P5-12 Density Collapse in Improved Confinement Mode on Tohoku University Heliac S. Kitajima 1), Y. Tanaka 2), H. Utoh 1), H. Umetsu 1), J. Sato 1), K. Ishii 1), T. Kobuchi 1), A. Okamoto 1), M. Sasao

More information

Recent results on non-inductive startup of highly overdense ST plasma by electron Bernstein wave on LATE

Recent results on non-inductive startup of highly overdense ST plasma by electron Bernstein wave on LATE Recent results on non-inductive startup of highly overdense ST plasma by electron Bernstein wave on LATE M. Uchida, Y. Nozawa, H. Tanaka, T. Maekawa Graduate School of Energy Science, Kyoto University

More information

Formation of An Advanced Tokamak Plasma without the Use of Ohmic Heating Solenoid in JT-60U

Formation of An Advanced Tokamak Plasma without the Use of Ohmic Heating Solenoid in JT-60U 1 Formation of An Advanced Tokamak Plasma without the Use of Ohmic Heating Solenoid in JT-60U Y. Takase, 1) S. Ide, 2) S. Itoh, 3) O. Mitarai, 4) O. Naito, 2) T. Ozeki, 2) Y. Sakamoto, 2) S. Shiraiwa,

More information

Flow and dynamo measurements in the HIST double pulsing CHI experiment

Flow and dynamo measurements in the HIST double pulsing CHI experiment Innovative Confinement Concepts (ICC) & US-Japan Compact Torus (CT) Plasma Workshop August 16-19, 211, Seattle, Washington HIST Flow and dynamo measurements in the HIST double pulsing CHI experiment M.

More information

Ion Heating Experiments Using Perpendicular Neutral Beam Injection in the Large Helical Device

Ion Heating Experiments Using Perpendicular Neutral Beam Injection in the Large Helical Device Ion Heating Experiments Using Perpendicular Neutral Beam Injection in the Large Helical Device Kenichi NAGAOKA, Masayuki YOKOYAMA, Yasuhiko TAKEIRI, Katsumi IDA, Mikiro YOSHINUMA, Seikichi MATSUOKA 1),

More information

Non-inductive plasma startup and current profile modification in Pegasus spherical torus discharges

Non-inductive plasma startup and current profile modification in Pegasus spherical torus discharges Non-inductive plasma startup and current profile modification in Pegasus spherical torus discharges Aaron J. Redd for the Pegasus Team 2008 Innovative Confinement Concepts Workshop Reno, Nevada June 24-27,

More information

Dynamics of ion internal transport barrier in LHD heliotron and JT-60U tokamak plasmas

Dynamics of ion internal transport barrier in LHD heliotron and JT-60U tokamak plasmas Dynamics of ion internal transport barrier in LHD heliotron and JT-60U tokamak plasmas K. Ida 1), Y. Sakamoto 2), M. Yoshinuma 1), H. Takenaga 2), K. Nagaoka 1), N. Oyama 2), M. Osakabe 1), M. Yokoyama

More information

Continuous, Localized Ion Heating due to Magnetic Reconnection in a Low Aspect Ratio Tokamak

Continuous, Localized Ion Heating due to Magnetic Reconnection in a Low Aspect Ratio Tokamak Continuous, Localized Ion Heating due to Magnetic Reconnection in a Low Aspect Ratio Tokamak M. G. Burke, J.L. Barr, M.W. Bongard, R.J. Fonck, E.T. Hinson, J.M. Perry, J.A. Reusch, D.J. Schlossberg EPR

More information

Observation of Neo-Classical Ion Pinch in the Electric Tokamak*

Observation of Neo-Classical Ion Pinch in the Electric Tokamak* 1 EX/P6-29 Observation of Neo-Classical Ion Pinch in the Electric Tokamak* R. J. Taylor, T. A. Carter, J.-L. Gauvreau, P.-A. Gourdain, A. Grossman, D. J. LaFonteese, D. C. Pace, L. W. Schmitz, A. E. White,

More information

High Beta Discharges with Hydrogen Storage Electrode Biasing in the Tohoku University Heliac

High Beta Discharges with Hydrogen Storage Electrode Biasing in the Tohoku University Heliac J. Plasma Fusion Res. SERIES, Vol. 8 (2009) High Beta Discharges with Hydrogen Storage Electrode Biasing in the Tohoku University Heliac Hiroyasu UTOH, Kiyohiko NISHIMURA 1), Hajime UMETSU, Keiichi ISHII,

More information

MAGNETIC NOZZLE PLASMA EXHAUST SIMULATION FOR THE VASIMR ADVANCED PROPULSION CONCEPT

MAGNETIC NOZZLE PLASMA EXHAUST SIMULATION FOR THE VASIMR ADVANCED PROPULSION CONCEPT MAGNETIC NOZZLE PLASMA EXHAUST SIMULATION FOR THE VASIMR ADVANCED PROPULSION CONCEPT ABSTRACT A. G. Tarditi and J. V. Shebalin Advanced Space Propulsion Laboratory NASA Johnson Space Center Houston, TX

More information

RESISTIVE WALL MODE STABILIZATION RESEARCH ON DIII D STATUS AND RECENT RESULTS

RESISTIVE WALL MODE STABILIZATION RESEARCH ON DIII D STATUS AND RECENT RESULTS RESISTIVE WALL MODE STABILIZATION RESEARCH ON STATUS AND RECENT RESULTS by A.M. Garofalo1 in collaboration with J. Bialek,1 M.S. Chance,2 M.S. Chu,3 T.H. Jensen,3 L.C. Johnson,2 R.J. La Haye,3 G.A. Navratil,1

More information

Advancing Local Helicity Injection for Non-Solenoidal Tokamak Startup

Advancing Local Helicity Injection for Non-Solenoidal Tokamak Startup Advancing Local Helicity Injection for Non-Solenoidal Tokamak Startup M.W. Bongard G.M. Bodner, M.G. Burke, R.J. Fonck, J.L. Pachicano, J.M. Perry, C. Pierren, J.A. Reusch, A.T. Rhodes, N.J. Richner, C.

More information

Formation of High-b ECH Plasma and Inward Particle Diffusion in RT-1

Formation of High-b ECH Plasma and Inward Particle Diffusion in RT-1 J Fusion Energ (2010) 29:553 557 DOI 10.1007/s10894-010-9327-6 ORIGINAL RESEARCH Formation of High-b ECH Plasma and Inward Particle Diffusion in RT-1 H. Saitoh Z. Yoshida J. Morikawa Y. Yano T. Mizushima

More information

Active Control of Alfvén Eigenmodes in the ASDEX Upgrade tokamak

Active Control of Alfvén Eigenmodes in the ASDEX Upgrade tokamak Active Control of Alfvén Eigenmodes in the ASDEX Upgrade tokamak M. Garcia-Munoz, S. E. Sharapov, J. Ayllon, B. Bobkov, L. Chen, R. Coelho, M. Dunne, J. Ferreira, A. Figueiredo, M. Fitzgerald, J. Galdon-Quiroga,

More information

Abstract. The Pegasus Toroidal Experiment is an ultra-low aspect ratio (A < 1.2) spherical tokamak (ST) capable of operating in the high I N

Abstract. The Pegasus Toroidal Experiment is an ultra-low aspect ratio (A < 1.2) spherical tokamak (ST) capable of operating in the high I N Abstract The Pegasus Toroidal Experiment is an ultra-low aspect ratio (A < 1.2) spherical tokamak (ST) capable of operating in the high I N regime (I N > 12). Access to this regime requires a small centerpost

More information

3-D Random Reconnection Model of the Sawtooth Crash

3-D Random Reconnection Model of the Sawtooth Crash 3-D Random Reconnection Model of the Sawtooth Crash Hyeon K. Park Princeton Plasma PhysicsN Laboratory Princeton University at IPELS, 2007 Cairns, Australia August 5-9, 2007 Collaboration with N.C. Luhmann,

More information

Characteristics of Internal Transport Barrier in JT-60U Reversed Shear Plasmas

Characteristics of Internal Transport Barrier in JT-60U Reversed Shear Plasmas Characteristics of Internal Transport Barrier in JT-6U Reversed Shear Plasmas Y. Sakamoto, Y. Kamada, S. Ide, T. Fujita, H. Shirai, T. Takizuka, Y. Koide, T. Fukuda, T. Oikawa, T. Suzuki, K. Shinohara,

More information

Special topic JPFR article Prospects of Research on Innovative Concepts in ITER Era contribution by M. Brown Section 5.2.2

Special topic JPFR article Prospects of Research on Innovative Concepts in ITER Era contribution by M. Brown Section 5.2.2 Special topic JPFR article Prospects of Research on Innovative Concepts in ITER Era contribution by M. Brown Section 5.2.2 5.2.2 Dynamo and Reconnection Research: Overview: Spheromaks undergo a relaxation

More information

HIFLUX: OBLATE FRCs, DOUBLE HELICES, SPHEROMAKS AND RFPs IN ONE SYSTEM

HIFLUX: OBLATE FRCs, DOUBLE HELICES, SPHEROMAKS AND RFPs IN ONE SYSTEM GA A24391 HIFLUX: OBLATE FRCs, DOUBLE HELICES, SPHEROMAKS AND RFPs IN ONE SYSTEM by M.J. SCHAFFER and J.A. BOEDO JULY 2003 QTYUIOP DISCLAIMER This report was prepared as an account of work sponsored by

More information

November 2, Monday. 17. Magnetic Energy Release

November 2, Monday. 17. Magnetic Energy Release November, Monday 17. Magnetic Energy Release Magnetic Energy Release 1. Solar Energetic Phenomena. Energy Equation 3. Two Types of Magnetic Energy Release 4. Rapid Dissipation: Sweet s Mechanism 5. Petschek

More information

MHD Simulation of Solar Chromospheric Evaporation Jets in the Oblique Coronal Magnetic Field

MHD Simulation of Solar Chromospheric Evaporation Jets in the Oblique Coronal Magnetic Field MHD Simulation of Solar Chromospheric Evaporation Jets in the Oblique Coronal Magnetic Field Y. Matsui, T. Yokoyama, H. Hotta and T. Saito Department of Earth and Planetary Science, University of Tokyo,

More information

Magnetic reconnection with Sweet-Parker characteristics in two-dimensional laboratory plasmas*

Magnetic reconnection with Sweet-Parker characteristics in two-dimensional laboratory plasmas* PHYSICS OF PLASMAS VOLUME 6, NUMBER 5 MAY 1999 Magnetic reconnection with Sweet-Parker characteristics in two-dimensional laboratory plasmas* Hantao Ji,,a) Masaaki Yamada, Scott Hsu, Russell Kulsrud, Troy

More information

Magnetic Reconnection with Sweet-Parker Characteristics in. Two-dimensional Laboratory Plasmas. Abstract

Magnetic Reconnection with Sweet-Parker Characteristics in. Two-dimensional Laboratory Plasmas. Abstract Magnetic Reconnection with Sweet-Parker Characteristics in Two-dimensional Laboratory Plasmas Hantao Ji, Masaaki Yamada, Scott Hsu, Russell Kulsrud, Troy Carter, and Sorin Zaharia Plasma Physics Laboratory,

More information

Stabilization of sawteeth in tokamaks with toroidal flows

Stabilization of sawteeth in tokamaks with toroidal flows PHYSICS OF PLASMAS VOLUME 9, NUMBER 7 JULY 2002 Stabilization of sawteeth in tokamaks with toroidal flows Robert G. Kleva and Parvez N. Guzdar Institute for Plasma Research, University of Maryland, College

More information

0 Magnetically Confined Plasma

0 Magnetically Confined Plasma 0 Magnetically Confined Plasma 0.1 Particle Motion in Prescribed Fields The equation of motion for species s (= e, i) is written as d v ( s m s dt = q s E + vs B). The motion in a constant magnetic field

More information

Comparison of Ion Internal Transport Barrier Formation between Hydrogen and Helium Dominated Plasmas )

Comparison of Ion Internal Transport Barrier Formation between Hydrogen and Helium Dominated Plasmas ) Comparison of Ion Internal Transport Barrier Formation between Hydrogen and Helium Dominated Plasmas ) Kenichi NAGAOKA 1,2), Hiromi TAKAHASHI 1,2), Kenji TANAKA 1), Masaki OSAKABE 1,2), Sadayoshi MURAKAMI

More information

The Effects of Noise and Time Delay on RWM Feedback System Performance

The Effects of Noise and Time Delay on RWM Feedback System Performance The Effects of Noise and Time Delay on RWM Feedback System Performance O. Katsuro-Hopkins, J. Bialek, G. Navratil (Department of Applied Physics and Applied Mathematics, Columbia University, New York,

More information

Soft X-ray emission profile and mode structure during MHD events in the TST-2 spherical tokamak

Soft X-ray emission profile and mode structure during MHD events in the TST-2 spherical tokamak P6-29 Soft X-ray emission profile and mode structure during MHD events in the TST-2 spherical tokamak H.Tojo, A.Ejiri, Y.Takase, Y.Torii, T.Osako, M.Sasaki (1), T.Masuda, Y.Shimada N.Sumitomo (1), J.Tsujimura,

More information

Overview of Tokamak Rotation and Momentum Transport Phenomenology and Motivations

Overview of Tokamak Rotation and Momentum Transport Phenomenology and Motivations Overview of Tokamak Rotation and Momentum Transport Phenomenology and Motivations Lecture by: P.H. Diamond Notes by: C.J. Lee March 19, 2014 Abstract Toroidal rotation is a key part of the design of ITER

More information

Numerical modeling of magnetohydrodynamic activity in the Swarthmore Spheromak Experiment

Numerical modeling of magnetohydrodynamic activity in the Swarthmore Spheromak Experiment PHYSICS OF PLASMAS VOLUME 8, NUMBER 5 MAY 2001 Numerical modeling of magnetohydrodynamic activity in the Swarthmore Spheromak Experiment V. S. Lukin a) Department of Physics and Astronomy, Swarthmore College,

More information

Driving Mechanism of SOL Plasma Flow and Effects on the Divertor Performance in JT-60U

Driving Mechanism of SOL Plasma Flow and Effects on the Divertor Performance in JT-60U EX/D-3 Driving Mechanism of SOL Plasma Flow and Effects on the Divertor Performance in JT-6U N. Asakura ), H. Takenaga ), S. Sakurai ), G.D. Porter ), T.D. Rognlien ), M.E. Rensink ), O. Naito ), K. Shimizu

More information

Design of next step tokamak: Consistent analysis of plasma flux consumption and poloidal field system

Design of next step tokamak: Consistent analysis of plasma flux consumption and poloidal field system Design of next step tokamak: Consistent analysis of plasma flux consumption and poloidal field system J.M. Ané 1, V. Grandgirard, F. Albajar 1, J.Johner 1 1Euratom-CEA Association, Cadarache, France Euratom-EPFL

More information

DT Fusion Ignition of LHD-Type Helical Reactor by Joule Heating Associated with Magnetic Axis Shift )

DT Fusion Ignition of LHD-Type Helical Reactor by Joule Heating Associated with Magnetic Axis Shift ) DT Fusion Ignition of LHD-Type Helical Reactor by Joule Heating Associated with Magnetic Axis Shift ) Tsuguhiro WATANABE National Institute for Fusion Science, 322-6 Oroshi-cho, Toki 509-5292, Japan (Received

More information

Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks

Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks J. W. Van Dam and L.-J. Zheng Institute for Fusion Studies University of Texas at Austin 12th US-EU Transport Task Force Annual

More information

Magnetic reconnection, merging flux ropes, 3D effects in RSX

Magnetic reconnection, merging flux ropes, 3D effects in RSX Magnetic reconnection, merging flux ropes, 3D effects in RSX T. Intrator P-24 I. Furno, E. Hemsing, S. Hsu, + many students G.Lapenta, P.Ricci T-15 Plasma Theory Second Workshop on Thin Current Sheets

More information

Nonsolenoidal Startup and Plasma Stability at Near-Unity Aspect Ratio in the Pegasus Toroidal Experiment

Nonsolenoidal Startup and Plasma Stability at Near-Unity Aspect Ratio in the Pegasus Toroidal Experiment 1 EXS/P2-07 Nonsolenoidal Startup and Plasma Stability at Near-Unity Aspect Ratio in the Pegasus Toroidal Experiment R.J. Fonck 1), D.J. Battaglia 2), M.W. Bongard 1), E.T. Hinson 1), A.J. Redd 1), D.J.

More information

(Inductive tokamak plasma initial start-up)

(Inductive tokamak plasma initial start-up) (Inductive tokamak plasma initial start-up) 24. 6. 7. (tapl1.kaist.ac.kr) Outline Conventional inductive tokamak plasma start-up Inductive outer PF coil-only plasma start-up Inductive plasma start-up in

More information

Progress of Confinement Physics Study in Compact Helical System

Progress of Confinement Physics Study in Compact Helical System 1st IAEA Fusion Energy Conference Chengdu, China, 16-1 October, 6 IAEA-CN-149/ EX/5-5Rb Progress of Confinement Physics Study in Compact Helical System S. Okamura et al. NIFS-839 Oct. 6 1 EX/5-5Rb Progress

More information

Plasmoid Motion in Helical Plasmas

Plasmoid Motion in Helical Plasmas Plasmoid Motion in Helical Plasmas Ryuichi ISHIZAKI and Noriyoshi NAKAJIMA National Institute for Fusion Science, Toki 509-5292, Japan (Received 12 December 2009 / Accepted 18 May 2010) In order to explain

More information

Lower Hybrid Current Drive Experiments on Alcator C-Mod: Comparison with Theory and Simulation

Lower Hybrid Current Drive Experiments on Alcator C-Mod: Comparison with Theory and Simulation Lower Hybrid Current Drive Experiments on Alcator C-Mod: Comparison with Theory and Simulation P.T. Bonoli, A. E. Hubbard, J. Ko, R. Parker, A.E. Schmidt, G. Wallace, J. C. Wright, and the Alcator C-Mod

More information

Study of High-energy Ion Tail Formation with Second Harmonic ICRF Heating and NBI in LHD

Study of High-energy Ion Tail Formation with Second Harmonic ICRF Heating and NBI in LHD 21st IAEA Fusion Energy Conference Chengdu, China, 16-21 October, 2006 IAEA-CN-149/ Study of High-energy Ion Tail Formation with Second Harmonic ICRF Heating and NBI in LHD K. Saito et al. NIFS-851 Oct.

More information

Turbulence Analysis of a Flux Rope Plasma on the Swarthmore Spheromak Experiment

Turbulence Analysis of a Flux Rope Plasma on the Swarthmore Spheromak Experiment Research supported by US DOE and NSF Turbulence Analysis of a Flux Rope Plasma on the Swarthmore Spheromak Experiment David Schaffner Swarthmore College, NSF Center for Magnetic Self-Organization with

More information

RWM FEEDBACK STABILIZATION IN DIII D: EXPERIMENT-THEORY COMPARISONS AND IMPLICATIONS FOR ITER

RWM FEEDBACK STABILIZATION IN DIII D: EXPERIMENT-THEORY COMPARISONS AND IMPLICATIONS FOR ITER GA A24759 RWM FEEDBACK STABILIZATION IN DIII D: EXPERIMENT-THEORY COMPARISONS AND IMPLICATIONS FOR ITER by A.M. GAROFALO, J. BIALEK, M.S. CHANCE, M.S. CHU, D.H. EDGELL, G.L. JACKSON, T.H. JENSEN, R.J.

More information

Derivation of dynamo current drive in a closed current volume and stable current sustainment in the HIT SI experiment

Derivation of dynamo current drive in a closed current volume and stable current sustainment in the HIT SI experiment Derivation of dynamo current drive and stable current sustainment in the HIT SI experiment 1 Derivation of dynamo current drive in a closed current volume and stable current sustainment in the HIT SI experiment

More information

Observations of Counter-Current Toroidal Rotation in Alcator C-Mod LHCD Plasmas

Observations of Counter-Current Toroidal Rotation in Alcator C-Mod LHCD Plasmas 1 EX/P5-4 Observations of Counter-Current Toroidal Rotation in Alcator C-Mod LHCD Plasmas J.E. Rice 1), A.C. Ince-Cushman 1), P.T. Bonoli 1), M.J. Greenwald 1), J.W. Hughes 1), R.R. Parker 1), M.L. Reinke

More information

Recent Development of LHD Experiment. O.Motojima for the LHD team National Institute for Fusion Science

Recent Development of LHD Experiment. O.Motojima for the LHD team National Institute for Fusion Science Recent Development of LHD Experiment O.Motojima for the LHD team National Institute for Fusion Science 4521 1 Primary goal of LHD project 1. Transport studies in sufficiently high n E T regime relevant

More information

Time-scales for Non-Inductive Current Buildup In Low-Aspect-Ratio Toroidal Geometry. S. C. Jardin. Abstract

Time-scales for Non-Inductive Current Buildup In Low-Aspect-Ratio Toroidal Geometry. S. C. Jardin. Abstract Time-scales for Non-Inductive Current Buildup In Low-Aspect-Ratio Toroidal Geometry S. C. Jardin Princeton Plasma Physics Laboratory Princeton University Princeton, NJ 08543 November 1999 Abstract The

More information

Three-dimensional MHD simulations of counter-helicity spheromak merging in the Swarthmore Spheromak Experiment

Three-dimensional MHD simulations of counter-helicity spheromak merging in the Swarthmore Spheromak Experiment Three-dimensional MHD simulations of counter-helicity spheromak merging in the Swarthmore Spheromak Experiment C. E. Myers, 1, a) E. V. Belova, 1 M. R. Brown, 2 T. Gray, 2 C. D. Cothran, 2, b) and M. J.

More information

Measurements of rotational transform due to noninductive toroidal current using motional Stark effect spectroscopy in the Large Helical Device

Measurements of rotational transform due to noninductive toroidal current using motional Stark effect spectroscopy in the Large Helical Device REVIEW OF SCIENTIFIC INSTRUMENTS 76, 053505 2005 Measurements of rotational transform due to noninductive toroidal current using motional Stark effect spectroscopy in the Large Helical Device K. Ida, a

More information

Integrated Heat Transport Simulation of High Ion Temperature Plasma of LHD

Integrated Heat Transport Simulation of High Ion Temperature Plasma of LHD 1 TH/P6-38 Integrated Heat Transport Simulation of High Ion Temperature Plasma of LHD S. Murakami 1, H. Yamaguchi 1, A. Sakai 1, K. Nagaoka 2, H. Takahashi 2, H. Nakano 2, M. Osakabe 2, K. Ida 2, M. Yoshinuma

More information

Role of the Electron Temperature in the Current Decay during Disruption in JT-60U )

Role of the Electron Temperature in the Current Decay during Disruption in JT-60U ) Role of the Electron Temperature in the Current Decay during Disruption in JT-60U ) Yoshihide SHIBATA, Akihiko ISAYAMA, Go MATSUNAGA, Yasunori KAWANO, Seiji MIYAMOTO 1), Victor LUKASH 2), Rustam KHAYRUTDINOV

More information

A Hybrid Inductive Scenario for a Pulsed- Burn RFP Reactor with Quasi-Steady Current. John Sarff

A Hybrid Inductive Scenario for a Pulsed- Burn RFP Reactor with Quasi-Steady Current. John Sarff A Hybrid Inductive Scenario for a Pulsed- Burn RFP Reactor with Quasi-Steady Current John Sarff 12th IEA RFP Workshop Kyoto Institute of Technology, Kyoto, Japan Mar 26-28, 2007 The RFP fusion development

More information

DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH

DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH by K.H. Burrell Presented at High Temperature Plasma Diagnostics 2 Conference Tucson, Arizona June 19 22, 2 134 /KHB/wj ROLE OF DIAGNOSTICS IN ADVANCED TOKAMAK

More information

Magnetic Reconnection: Recent Developments and Future Challenges

Magnetic Reconnection: Recent Developments and Future Challenges Magnetic Reconnection: Recent Developments and Future Challenges A. Bhattacharjee Center for Integrated Computation and Analysis of Reconnection and Turbulence (CICART) Space Science Center, University

More information

Comparison of Pellet Injection Measurements with a Pellet Cloud Drift Model on the DIII-D Tokamak

Comparison of Pellet Injection Measurements with a Pellet Cloud Drift Model on the DIII-D Tokamak Comparison of Pellet Injection Measurements with a Pellet Cloud Drift Model on the DIII-D Tokamak T.C. Jernigan, L.R. Baylor, S.K. Combs, W.A. Houlberg (Oak Ridge National Laboratory) P.B. Parks (General

More information

Transport Improvement Near Low Order Rational q Surfaces in DIII D

Transport Improvement Near Low Order Rational q Surfaces in DIII D Transport Improvement Near Low Order Rational q Surfaces in DIII D M.E. Austin 1 With K.H. Burrell 2, R.E. Waltz 2, K.W. Gentle 1, E.J. Doyle 8, P. Gohil 2, C.M. Greenfield 2, R.J. Groebner 2, W.W. Heidbrink

More information

Electrode and Limiter Biasing Experiments on the Tokamak ISTTOK

Electrode and Limiter Biasing Experiments on the Tokamak ISTTOK Electrode and Limiter Biasing Experiments on the Tokamak ISTTOK C. Silva, H. Figueiredo, J.A.C. Cabral,, I. Nedzelsky, C.A.F. Varandas Associação Euratom/IST, Centro de Fusão Nuclear, Instituto Superior

More information

The Field-Reversed Configuration (FRC) is a high-beta compact toroidal in which the external field is reversed on axis by azimuthal plasma The FRC is

The Field-Reversed Configuration (FRC) is a high-beta compact toroidal in which the external field is reversed on axis by azimuthal plasma The FRC is and Stability of Field-Reversed Equilibrium with Toroidal Field Configurations Atomics General Box 85608, San Diego, California 92186-5608 P.O. APS Annual APS Meeting of the Division of Plasma Physics

More information

ª 10 KeV. In 2XIIB and the tandem mirrors built to date, in which the plug radius R p. ª r Li

ª 10 KeV. In 2XIIB and the tandem mirrors built to date, in which the plug radius R p. ª r Li Axisymmetric Tandem Mirrors: Stabilization and Confinement Studies R. F. Post, T. K. Fowler*, R. Bulmer, J. Byers, D. Hua, L. Tung Lawrence Livermore National Laboratory *Consultant, Presenter This talk

More information

HIGH PERFORMANCE EXPERIMENTS IN JT-60U REVERSED SHEAR DISCHARGES

HIGH PERFORMANCE EXPERIMENTS IN JT-60U REVERSED SHEAR DISCHARGES HIGH PERFORMANCE EXPERIMENTS IN JT-U REVERSED SHEAR DISCHARGES IAEA-CN-9/EX/ T. FUJITA, Y. KAMADA, S. ISHIDA, Y. NEYATANI, T. OIKAWA, S. IDE, S. TAKEJI, Y. KOIDE, A. ISAYAMA, T. FUKUDA, T. HATAE, Y. ISHII,

More information

Predictive Study on High Performance Modes of Operation in HL-2A 1

Predictive Study on High Performance Modes of Operation in HL-2A 1 1 EX/P-0 Predictive Study on High Performance Modes of Oration in HL-A 1 Qingdi GAO 1), R. V. BUDNY ), Fangzhu LI 1), Jinhua ZHANG 1), Hongng QU 1) 1) Southwestern Institute of Physics, Chengdu, Sichuan,

More information

Estimations of Beam-Beam Fusion Reaction Rates in the Deuterium Plasma Experiment on LHD )

Estimations of Beam-Beam Fusion Reaction Rates in the Deuterium Plasma Experiment on LHD ) Estimations of Beam-Beam Fusion Reaction Rates in the Deuterium Plasma Experiment on LHD ) Masayuki HOMMA, Sadayoshi MURAKAMI, Hideo NUGA and Hiroyuki YAMAGUCHI Department of Nuclear Engineering, Kyoto

More information

Bifurcation-Like Behavior of Electrostatic Potential in LHD )

Bifurcation-Like Behavior of Electrostatic Potential in LHD ) Bifurcation-Like Behavior of Electrostatic Potential in LHD ) Akihiro SHIMIZU, Takeshi IDO, Masaki NISHIURA, Ryohei MAKINO 1), Masayuki YOKOYAMA, Hiromi TAKAHASHI, Hiroe IGAMI, Yasuo YOSHIMURA, Shin KUBO,

More information

Fractal Structure (Turbulence) and SOC of a Current Sheet in a Solar Flare via Dynamic Magnetic Reconnection

Fractal Structure (Turbulence) and SOC of a Current Sheet in a Solar Flare via Dynamic Magnetic Reconnection 16-20 Sep 2013 ISSI team meating@bern ``Turbulence and Self-Organized Criticality 17 Sep 2013 (Tue), 09:30h-10:30h Fractal Structure (Turbulence) and SOC of a Current Sheet in a Solar Flare via Dynamic

More information

Triggering Mechanisms for Transport Barriers

Triggering Mechanisms for Transport Barriers Triggering Mechanisms for Transport Barriers O. Dumbrajs, J. Heikkinen 1, S. Karttunen 1, T. Kiviniemi, T. Kurki-Suonio, M. Mantsinen, K. Rantamäki 1, S. Saarelma, R. Salomaa, S. Sipilä, T. Tala 1 Euratom-TEKES

More information

Advanced Tokamak Research in JT-60U and JT-60SA

Advanced Tokamak Research in JT-60U and JT-60SA I-07 Advanced Tokamak Research in and JT-60SA A. Isayama for the JT-60 team 18th International Toki Conference (ITC18) December 9-12, 2008 Ceratopia Toki, Toki Gifu JAPAN Contents Advanced tokamak development

More information

Ion Heating During Local Helicity Injection Plasma Startup in the Pegasus ST

Ion Heating During Local Helicity Injection Plasma Startup in the Pegasus ST Ion Heating During Local Helicity Injection Plasma Startup in the Pegasus ST M.G. Burke, J.L. Barr, M.W. Bongard, R.J. Fonck, E.T. Hinson, J.M. Perry, J.A. Reusch 57 th Annual Meeting of the APS-DPP University

More information

Theory and MHD simulation of fuelling process by compact toroid (CT) injection

Theory and MHD simulation of fuelling process by compact toroid (CT) injection Theory and MHD simulation of fuelling process by compact toroid (CT) injection Y. SUZUKI 1), T. HAYASHI 2), Y. KISHIMOTO 1) 1) Plasma Theory Laboratory, Department of Fusion Plasma Research, Naka Fusion

More information

Oscillating-Field Current-Drive Experiment on MST

Oscillating-Field Current-Drive Experiment on MST Oscillating-Field Current-Drive Experiment on MST K. J. McCollam, J. K. Anderson, D. J. Den Hartog, F. Ebrahimi, J. A. Reusch, J. S. Sarff, H. D. Stephens, D. R. Stone University of Wisconsin-Madison D.

More information

Energetic-Ion-Driven MHD Instab. & Transport: Simulation Methods, V&V and Predictions

Energetic-Ion-Driven MHD Instab. & Transport: Simulation Methods, V&V and Predictions Energetic-Ion-Driven MHD Instab. & Transport: Simulation Methods, V&V and Predictions 7th APTWG Intl. Conference 5-8 June 2017 Nagoya Univ., Nagoya, Japan Andreas Bierwage, Yasushi Todo 14.1MeV 10 kev

More information

Advancing Toward Reactor Relevant Startup via Localized Helicity Injection at the Pegasus Toroidal Experiment

Advancing Toward Reactor Relevant Startup via Localized Helicity Injection at the Pegasus Toroidal Experiment Advancing Toward Reactor Relevant Startup via Localized Helicity Injection at the Pegasus Toroidal Experiment E. T. Hinson J. L. Barr, M. W. Bongard, M. G. Burke, R. J. Fonck, J. M. Perry, A. J. Redd,

More information